ML20128P676
| ML20128P676 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 06/30/1985 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML19304B384 | List:
|
| References | |
| NUDOCS 8507260478 | |
| Download: ML20128P676 (6) | |
Text
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
The Westinghouse Electric Corporation (hereinafter referred to as Westinghouse) has developed this Reference Safety Analysis Report (RESAR-SP/90) for the Westinghouse Advanced Pressurized Water Reactor (WAPWR) as part of its continuing efforts toward design and licensing standardization of nuclear power plants.
RESAR-SP/90 is a standard safety analysis report submitted initially for Preliminary Design Approval (PDA) in accordance with Appendix 0, " Standardization of Design; Staff Review of Standard Designs," to Part 50 of Title 10 of the Code of Federal Regulations (hereinafter referred to as 10CFR).
The ultimate objective is to obtain a Final Design Approval (FDA) of RESAR-SP/90 followed by a rulemaking proceeding and design certification.
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WAPWR-RP 1.1-1 JUNE, 1985 2997e:1d 8507260478 850712 ADOCK0500g1 DR
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1.2 GENERAL PLANT DESCRIPTION 1.2.2 Principal Desian Criteria i
RESAR-SP/90 is designed to comply with 10 CFR Part 50, Appendix 'A,
" General Design Criteria for Nuclear Power Plants."
The specific applications of l
General Design Criteria to RESAR-SP/90 are discussed in Section 3.1 of RESAR-SP/90 Module 7. " Structural / Equipment Design.
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WAPWR-RP 1.2-1 JUNE, 1985 t
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f 1.6 MATERIAL INCORPORATED BY REFERENCE The WAPWR Radiation Protection Module incorporates, by reference, certain topical reports.
The topical reports, listed in Table 1.6-1, have been filed d
previously in support of other Westinghouse applications.
The legend for the review status code letter follows:
U.S.
Nuclear Regulatory Connission review complete; USNRC A
acceptance letter issued.
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U.S.
Nuclear Regulatory Connission accepted as part of the i
AE Westinghouse emergency core cooling system (ECCS) evaluation model only; does not constitute acceptance for any purpose other than for ECCS analyses.
8 Submitted to USNRC as background information; no undergoing formal USNRC review.
i On file with USNRC: older generation report with current validity; 0
not actively under formal USNRC review.
9-Actively under formal USNRC review.
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TABLE 1.6-1 MATERIAL INCORPORATED BY REFERENCE i
Westinghouse SAR Topical Revision Section Submitted Reviet Report No.
Title Number Reference to the NRC Statu!
WCAP-8370 Westinghouse Water Reactor Divi-Rev. 9A 17.1 2/81 A
sions Quality Assurance Plan Amend. 1 i
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1.8 CONFORMANCE WITH THE STANDARD REVIEW PLAN 4
In accordance with 10CFR50.34(g), Table 1.8-1 of each PDA module identifies
-and evaluates deviations from the acceptance criteria of those sec,tions of the NRC Standard Review Plan (NUREG-0800) pertinent to the subject module.
Table 1.8-1 provides this list for the " Radiation Protection".
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WAPWR-RP 1.8-l JUNE,1985 2997e:1d I
r TABLE 1.8-1 STANDARD REVIEW PLAN DEVIATIONS SRP Acceptance Criteria Deviation Section SRP 12.3 ?
The design of the fuel pool 12.3.4.1
(
racks precludes criticality 12.4 Describe the radiation instru-under all postulated normal mentation that will be used to and accident conditions. There-meet the criticality accident fore, criticality monitors, monitoring requirements of as required by 10 CFR 70.24 5 70.24 of 10 CFR Part 70 for and Regulatory Guide 8.12, are storage area for new fuel.
not needed.
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WAPWR-RP 1.B-2 JUNE, 1985 2997e:1d
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